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MONTHYEARML13133A0332013-05-0303 May 2013 License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink. Project stage: Request ML13133A0322013-05-0303 May 2013 License Amendment Request for Changes to Technical Specification 3/4.7.5 Ultimate Heat Sink. Project stage: Request ML13170A4772013-06-26026 June 2013 Millstone Power Station, Unit Nos. 2 and 3 - Acceptance Review Results Regarding Ultimate Heat Sink License Amendment Request (TAC Nos. MF1779 and MF1780) Project stage: Acceptance Review ML13197A4012013-07-18018 July 2013 Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.7.11 Ultimate Heat Sink. Project stage: RAI ML13204A0352013-07-19019 July 2013 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 4/4.7.11, Ultimate Heat Sink Project stage: Response to RAI ML13213A0242013-07-30030 July 2013 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink. Project stage: Response to RAI ML13192A2402013-07-30030 July 2013 Acceptance Review Results Regarding Ultimate Heat Sink License Amendment Requests Project stage: Acceptance Review ML13219A1092013-08-0101 August 2013 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink. Project stage: Response to RAI ML13281A8092013-10-0202 October 2013 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink Project stage: Response to RAI ML13347B0932013-12-19019 December 2013 Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.7.5 Ultimate Heat Sink Project stage: RAI ML14023A6462014-01-15015 January 2014 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink. Project stage: Response to RAI ML16015A1652014-04-18018 April 2014 Official Exhibit - NRC-043-00-BD01 - Letter from James Kim, Project Manager, NRC, to David A. Heacock, President and Chief Nuclear Officer, Dominion Nuclear, Millstone Power Station, Unit No. 2 - Issuance of Amendment Revise Technical . . Project stage: Approval ML15314A5762014-04-18018 April 2014 NRC-043 - Letter from James Kim, Project Manager, N.R.C., to David A. Heacock, President and Chief Nuclear Officer, Dominion Nuclear, Millstone Power Station, Unit No. 2 - Issuance of Amendment Revise Technical Specification 3/4.7.11 ... Project stage: Approval ML14037A4082014-04-18018 April 2014 Issuance of Amendment Revise Technical Specification 3/4.7.11 Ultimate Heat Sink Project stage: Approval ML14139A1002014-05-19019 May 2014 LAR Ultimate Heat Sink Project stage: Other ML14154A0912014-05-28028 May 2014 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink. Project stage: Response to RAI ML14178A5992014-07-11011 July 2014 Issuance of Amendment Proposed Changes to Technical Specification 3/4 7.5, Ultimate Heat Sink (Tac MF1780) Project stage: Approval 2013-07-30
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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24162A0882024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 ML24141A1502024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2272024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification ML24093A2162024-04-0101 April 2024 Response to Request for Additional Information Regarding License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 ML24092A0752024-03-28028 March 2024 3R22 Refueling Outage Inservice Inspection (ISI) Owners Activity Report Extension ML24088A2352024-03-26026 March 2024 Decommissioning Funding Status Report ML24086A4762024-03-22022 March 2024 Application for Technical Specification Change to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line-Item Improvement Process ML24086A4802024-03-22022 March 2024 Alternative Request IR-4-14, Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examination for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles ML24051A1922024-03-0808 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000336/20230062024-02-28028 February 2024 Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006) ML24053A2632024-02-21021 February 2024 Unit 3, and Independent Spent Fuel Storage Installation, Notification Pursuant to 10 CFR 72.212(b)(1) Prior to First Storage of Spent Fuel Under a General License ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage 2024-09-04
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 June 26,2013 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 -ACCEPTANCE REVIEW RESULTS REGARDING ULTIMATE HEAT SINK LICENSE AMENDMENT REQUEST (TAC NOS. MF1779 AND MF1780)
Dear Mr. Heacock:
By letter dated May 3,2013, Dominion Nuclear Connecticut, Inc., the licensee, submitted a license amendment request (LAR) to increase the current ultimate heat sink water temperature limit from 75 degrees Fahrenheit to 80 degrees Fahrenheit for Millstone Power Station, Unit Nos. 2 and 3 (Millstone).
The purpose of this letter is to provide the results of the Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license, including the technical specifications, must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications.
Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the application address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
In order to make the application complete, the NRC staff requests that the licensee supplement the application to address the information requested in the enclosure by July 3, 2013. This will enable the NRC staff to complete its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC staff will cease its review activities associated with the application.
If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
The information requested and associated time frame in this letter was discussed with Bill Bartron of your staff on June 20, 2013.
D. Heacock -2 If you have any questions regarding this issue, please contact me at (301)
/ /7/ . / ! // ..,-'/,/ Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423
Enclosure:
As stated cc w/encl: Distribution via Listserv SUPPLEMENTAL REGARDING ULTIMATE HEAT LICENSE AMENDMENT DOMINION NUCLEAR CONNECTICUT, MILLSTONE POWER STATION, UNIT NOS. 2 AND DOCKET NOS. 50-336 AND By letter dated May 3, 2013 (Agencywide Documents Access and Management Systems Accession No. ML 13133A032 and ML 13133A033), Dominion Nuclear Connecticut, Inc. submitted a license amendment request to increase the current ultimate heat sink water temperature limit from 75 degrees Fahrenheit CF) to 80 OF for Millstone Power Station, Unit Nos. 2 and 3. In order to complete its acceptance review, the Nuclear Regulatory Commission staff needs the following additional information: Please provide the following information for each safety related heat exchanger cooled by service water: 1. Design heat load 2. Design fouling factor 3. As-tested fouling factor 4. Tube plug allowance
- 5. Actual number of plugged tubes 6. Calculated heat removal capability
- 7. Design minimum flow rate 8. Actual flow rate 9. Vendor supplied heat exchanger specification sheet 10. Description of Generic Letter 89-13 testing/cleaning program for each heat exchanger Provide an 18" x 24" piping and instrumentation diagram of the service water system. Please state whether or not the increase in service water temperature from 75 OF to 80 OF will result in a derating of the emergency diesel generators.
Enclosure D. Heacock -2 If you have any questions regarding this issue, please contact me at (301) 415-1016.
Sincerely, Ira! Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsN rrDorlLpl1-1 RidsNrrPM Millstone LPL 1-1 RtF RidsNrrLAKGoldstein RidsAcrsAcnw_MailCTR RidsNrrDorlDpr RidsRgn1 MailCenter GPurciarello, NRR RidsOGCMailCenter RidsNrrDssSbpb RWolfgang, NRR RisNrrDeEpnb PSahay. NRR RidsNrrDeEeeb GCooper, NRR RidsNrrDraAfpb BTitus. NRR MHamm, NRR RidsNrrDssStsb KBucholtz.
NRR ADAMS Accession No.: ML13170A477
- See email dated June 13, 2013 I'OFFICE LPLI-1IPM LPLI-1/LA DSS/SBPB/BC LPLI*1/BC , NAME NMorgan KG old stein GCasto RBeall (A) DATE 6/25/13 6/21/13 6/13/2013*
6/26/13 OFFICIAL RECORD COpy